William A. Hanson

Idaho National Laboratory — United States

Materials Science · Physical Sciences

15h-index1.4kcitations44works1.42yr avg
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Research Topics

Nuclear Materials and Properties(13), Nuclear reactor physics and engineering(11), Fusion materials and technologies(7), Orthopaedic implants and arthroplasty(5), Soft Robotics and Applications(5)

Publications43 total

Effects of ZrN coating and heat treatment on U-Mo dispersion fuel systems under irradiation
Journal of Nuclear Materials·2025
Thermal conductivity measurement of U-Mo and U-Mo/Al interaction layers generated from in-pile irradiation using the suspended-bridge method
Scripta Materialia·2025
Precision Local Burnup Assessment Through Dynamic Peak Fitting in Atom Probe Tomography for Depleted, Enriched, and Irradiated Metallic and Ceramic Fuels
Microscopy and Microanalysis·2025· 1 cited
Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates
Journal of Nuclear Materials·2025· 1 citedOpen Access
Automated Burnup Analysis from Metallic, Ceramic, and Amorphous Fuels using Atom Probe Tomography
Microscopy and Microanalysis·2024· 2 cited
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
Journal of Nuclear Engineering and Radiation Science·2024· 5 citedOpen Access
Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
Journal of Nuclear Materials·2023· 3 citedOpen Access
Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels
Journal of Nuclear Materials·2023· 8 citedOpen Access
Channel Gap Measurements of Irradiated Plate Fuel and Comparison with Post-Irradiation Plate Thickness
Nuclear Engineering and Technology·2023· 4 citedOpen Access
Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels
Journal of Nuclear Materials·2023· 3 citedOpen Access
Post-irradiation Examination Status for the BSU-269 Project
2022Open Access
Non-destructive analysis of swelling in the EMPIrE fuel test
Journal of Nuclear Materials·2022· 11 citedOpen Access
Application of HPLC to Dissolution Testing of Solid Dosage Forms
2022· 2 cited
Swelling of U-Mo Monolithic Fuel: Developing a Predictive Swelling Correlation under Research Reactor Conditions
Journal of Nuclear Materials·2020· 27 citedOpen Access
The CORAL supercomputer systems
IBM Journal of Research and Development·2019· 20 cited
Ionizing vs collisional radiation damage in materials: Separated, competing, and synergistic effects in Ti3SiC2
Acta Materialia·2019· 19 citedOpen Access
Analysis of the Gálvez-Davison Index for Convective Forecasting Over Africa Using the GALWEM
2019
The Response of Ti3SiC2 MAX Phase to Ion Energy Dissipation During Energetic Irradiations at Different Temperatures
2019· 1 cited
Influence of electronic vs nuclear energy loss in radiation damage of Ti3SiC2
Acta Materialia·2018· 15 citedOpen Access
Prosthetic Jamming Terminal Device: A Case Study of Untethered Soft Robotics
Soft Robotics·2016· 50 citedOpen Access
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Frequent Co-authors

B.L. Musits(7), Russell H. Taylor(6), H. Paul(6), Peter Kazanzides(6), J. Zuhars(6), William L. Bargar(6), Daniele Salvato(6), Brent Mittelstadt(5), Bill Williamson(5), Adam Robinson(5), E. Glassman(4), Dennis D. Keiser(4), Mukesh Bachhav(4), Jian Gan(4), B. Mittlestadt(3), Nancy Lybeck(3), Laura Jamison(3), Abdellatif M. Yacout(3), Charlyne Smith(3), Ralph Bernstein(3)